ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
DOE selects TVA and Holtec for SMR awards
The Department of Energy has selected the Tennessee Valley Authority and Holtec Government Services to support the early deployments of light water small modular reactors in the United States. The companies will each receive as much as $400 million in federal cost-shared funding to advance their initial SMR projects in Tennessee and Michigan, respectively, including follow-on projects and associated supply chains.
Hubertus Nickel, Florian Schubert
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 649-660
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33486
Articles are hosted by Taylor and Francis Online.
Based on the existing structural design code for pressure vessel and nuclear light water reactor power stations, situations for metallic structures in hightemperature gas-cooled reactors (HTGRs) are described for those metallic structures that mainly operate in temperature ranges of time-independent and time-dependent materials properties. The ASME Code Case N 47 is critically reviewed. For advanced HTGRs with components for operating temperatures >800°C, no nuclear accepted structural design code exists. The status of the ongoing work for the basis of those codes is given with the main emphasis on the situation in the Federal Republic of Germany.
